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An Assessment of Reactor Vessel Integrity Under In-Vessel Vapor Explosion Loads
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  • An Assessment of Reactor Vessel Integrity Under In-Vessel Vapor Explosion Loads
  • An Assessment of Reactor Vessel Integrity Under In-Vessel Vapor Explosion Loads
저자명
Bang. Kwang-Hyun,Cho. Jong-Rae,Park. Soo-Yong
간행물명
Journal of the Korean Nuclear Society
권/호정보
2000년|32권 4호|pp.299-308 (10 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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기타
이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
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기타언어초록

A safety assessment of reactor vessel lower head integrity under in-vessel vapor explosion loads has been performed. The core melt relocation parameters were chosen within the ranges of physically realizable bounds. The premixing and explosion calculations were performed using TRACER-II code. Using the calculated explosion pressures imposed on the lower head inner wall, strain calculations were peformed using ANSYS code. Then, the calculated strain results and the established failure criteria were used in determining the failure probability of the lower head, In the explosion analyses, it is shown that the explosion impulses are not altered significantly by the uncertain parameters of triggering location and time, fuel and vapor volume fractions in uniform premixture bounding calculations. Strain analyses show that the vapor explosion-induced lower head failure is not possible under the present framework of assessment. The result of static analysis using the conservative explosion-end pressure of 50 MPa also supports the conclusion. It is recommended, however, that an assessment of fracture mechanics for preexisting cracks be also considered to obtain a more concrete conclusion.